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윤한기(Hanki Yoon),조승연(Seongyeon Cho),정용환(Yonghan Jeong) 대한기계학회 2012 대한기계학회 춘추학술대회 Vol.2012 No.2
Testing blanket concept in the integrated fusion environment is one of the principal objective of ITER. Blanket test modules will be intended in ITER from its operation and will be provide the first experimented data on the feasibility of the D-T cycle for fusion. In the Dual Coolant Lead Lithium(DCLL) blanket, the key element is the Flow Channel Insert(FCI) made of a silicon carbide and composite(SiCf/SiC), which serves as electric and thermal insulator. Therefore, the idea of using FCI as both electric and thermal insulator takes center place in ITER blanket concept, with Pb-17Li as a breeder and SiC ceramic and ferrite steel as a structural material. In this specials session, the trend of the design concept and R&D of fusion blanket material are introduced.